ML20137B654

Requests Withdrawal of Suppl 1 to Proposed Change 77 to Tech Specs & Unapproved Portions of Proposed Change 70.Submittals Intended to Comply w/NUREG-0313 Except for Reactor Coolant Leakage Limits

ML20137B654
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	01/06/1986
From:	Murphy W VERMONT YANKEE NUCLEAR POWER CORP.
To:	Bernero R Office of Nuclear Reactor Regulation
References
RTR-NUREG-0313, RTR-NUREG-313 FVY-86-2, NUDOCS 8601160010
Download: ML20137B654 (2)

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VERMONT YANKEE NUCLEAR POWER CORPORATION Y 86-2 RD 5, Box 169, Ferry Road, Brattleboro, VT 05301

. g ENGINEERING OFFICE 1671 WORCESTER ROAD FRAMINGHAM, MASSACHUSETTS 01701 TELEPHONE 6 t t-872-8100 January 6, 1986 U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attn:

Office of Nuclear Reactor Regulation Mr. R.M. Bernero, Jr., Director Division of BWR Licensing

References:

a)

License No. DPR-28 (Docket No. 50-271) b)

Letter, USNRC to All BWR Licensees, Implementation of NUREG 0313, Revision 1 (Generic Letter 81-04), dated 2/26/81 c)

Letter, VYNPC to USNRC, FVY 82-39, Proposed Change No. 77 to Technical Specifications, Supplement No. 1, dated 4/8/82 d)

Letter, VYNPC to USNRC, Proposed Change No. 77 to Technical Specifications, dated 1/30/79 e)

Letter, VYNPC to USNRC, Proposed Change No. 70 to Technical Specifications, dated 12/29/77 (Items I and II only) f)

NUREG 0313, Revision 1, Technical Report on Material Salection and Processing Guidelines for BWR Coolant Pressure Boundary Piping, dated July 1980 g)

IE Bulletin No. 83-02, Stress Corrosion Cracking in Large Diameter Stainless Steel Recirculation System Piping at BWR Plants, dated 3/4/83 h)

Letter, USNRC to All Licensees, Inspection of BWR Stainless Steel Piping (Generic Letter 84-11), dated 4/19/84 i)

Letter, USNRC to VYNPC, Safety Evaluation of the Implementation of NUREG 0313, Revision 1, dated 6/15/84 j)

Letter, USNRC to VYNPC, Order Confirming License Commitments on Pipe Crack Related Issues, dated 8/28/84

Subject:

Withdrawal of Technical Specification Proposed Change No. 77, Supplement 1, and Unapproved Portions of Proposed Change No. 70 The purpose of this letter is to request withdrawal of References c) and e) from further NRC consideration.

These submittals had been intended to bring our facility into compliance with the intent of NUREG 0313, with certain exceptions regarding reactor coolant leakage limits, but have since been superseded by more stringent commitments.

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VERMONT YANKEE NUCLEAR POWER CORPORATION U.S. Nuclear Regulatory Commissi n 9

January 6, 1986 Page 2 By letter dated June 15, 1984 (Reference i)], the NRC issued a Safety Evaluation Report addressing Vermont Yankee's position regarding NUREG 0313, Revision 1.

One conclusion of the SER was that, although our position did not fully meet the NRC's guidelines, "the assessment regarding conformance with'

-NUREG 0313, Revision 1, is not currently germane".because of more recent deve-lopments in the BWR stainless steel pipe cracking issue.

Subsequently, the NRC issued Reference j), which ordered, in part, that Vermont Yankee perform repla-cement of all reactor recirculation and residual heat removal system stainless steel piping during the 1985 refueling outage, and that we operate the reactor until that outage in accordance with the tightened reactor coolant leakage limits shown in the attachment to Reference j).

Because these measures and the augmented piping examinations performed under References g) and h) resulted from our response to NRC directives regarding Intergranular Stress Corrosion Cracking in critical piping systems, we believe that we have in effect complied with the intent of NUREG 0313.

Proposed l Change No. 77, Supplement 1, and the balance of Proposed Change No. 70 should therefore be withdrawn.

(Reference d) will remain as presently docketed.]

Accordingly, we request that you remove References c) and e) from further

~ consideration. We further request that the review of Reference d) be expedited to support our recent Inservice Inspection Program update, and to satisfy the requirements of 10CFR50.55a(g)(5)(ii).

We trust that the foregoing will meet with your approval; however, should you have any questions or require additional information, please contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION

/ Nan L

Warren P.

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Vice President and v

Manager of Operations

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